PDuke Energy. D.M. JAMIL Vice President Catawba Nuclear Station 4800 Concord Rd. / CN01 VP York, SC 29745-9635 803 831 4251 803 831 3221 fax July 18, 2006 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Subject: Duke Power Company LLC d/b/a Duke Energy Carolinas, LLC (Duke) Catawba Nuclear Station, Unit 2 Docket Number 50-414 Steam Generator Outage Summary Inservice Inspection Report for End of Cycle 14 Refueling Outage Please find attached the subject report which provides the results of the steam generator tube inservice inspection effort associated with the subject outage. There are no regulatory commitments contained in this letter or its attachment. If you have any questions concerning this material, please call L.J. Rudy at (803) 831-3084. Very truly yours, D.M. Jamil LJR/s Attachment A oct:7 www. duke-energy. corn
U.S. Nuclear Regulatory CommissionAttention: Document Control DeskWashington, D.C. 20555
Subject: Duke Power Company LLC d/b/a Duke EnergyCarolinas, LLC (Duke)Catawba Nuclear Station, Unit 2Docket Number 50-414Steam Generator Outage Summary InserviceInspection Report for End of Cycle 14Refueling Outage
Please find attached the subject report which provides theresults of the steam generator tube inservice inspectioneffort associated with the subject outage.
There are no regulatory commitments contained in this letteror its attachment.
If you have any questions concerning this material, pleasecall L.J. Rudy at (803) 831-3084.
Very truly yours,
D.M. Jamil
LJR/s
Attachment
A oct:7
www. duke-energy. corn
Document Control DeskPage 2July 18, 2006
xc (with attachment):
W.D. Travers, Regional AdministratorU.S. Nuclear Regulatory Commission, Region IIAtlanta Federal Center61 Forsyth St., SW, Suite 23T85Atlanta, GA 30303
E.F. Guthrie, Senior Resident InspectorU.S. Nuclear Regulatory CommissionCatawba Nuclear Station
2 Hartford Steam BoilerInspection and InsuranceCo. (AIA)
Electronic Steam GeneratorDesktop
Page 1 of 20
FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS
As required by the Provisions of the ASME Code Rules
1. Owner: Duke Energy Corporation, 526 S. Church St.. Charlotte, NC 28201-1006(Name and Address of Owner)
2. Plant: Catawba Nuclear Station, 4800 Concord Road, York, S. C. 29745(Name and Address of Plant)
3.
4.
5.
6.
7.
Plant Unit: 2
Owner Certificate of Authorization (if required)
Commercial Service Date: Augrust 19, 1986
National Board Number for Unit 173
Components Inspected:
N/A
Component Manufacturer
Steam Generator 2A Westinghouse
Steam Generator 2B Westinghouse
Steam Generator 2C Westinghouse
Steam Generator 2D Westinghouse
Manufacturer State or NationalSerial No. Province No. Board No.
1923 N/A 4
1922 N/A 3
1921 N/A 2
1924 N/A 5
Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is81/2 in. x 11 in., (2) information in items 1 through 6 on this data report is included on each sheet, and(3) each sheet is numbered and the number of sheets is recorded at the top of this form.
Page 2 of 20
FORM NIS-1 (Back)
8. Examination Dates 10/24/2004 to 04/24/2006
9. Inspection Period Identification:
10. Inspection Interval Identification:
11. Applicable Edition of Section XI
12. Date/Revision of Inspection Plan:
#3
#2
1989 Addenda None
Per Technical Specification (5.5.9)
13. Abstract of Examinations and Test. Include a list of examinations and tests and a statementconcerning status of work required for the Inspection Plan.
14. Abstract of Results of Examination and Tests.
15. Abstract of Corrective Measures.
We certify that a) the statements made in this report are correct b) the examinations and tests meetthe Inspection Plan as required by the ASME Code, Section XI, and c) corrective measures takenconform to the rules of the ASME Code, Section XI.
Certificate of Authorization No. (if applicable) NA Expiration Date NA
Date U4',j 1'3 20 104 Signed Duke Energy Corp. By ! •/i 4t-e"
CERTIFICATE OF INSERVICE INSPECTION
[, the undersigned,iholding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State of Province of NC employed by *The HartfordSteam Boiler Inspection and Insurance Company of Connecticut have inspected the componentsdescribed in this Owners' Report during the period 03/27/2006 to 07/13/2006and state that to the best of my knowledge and belief, the Owner has performed examinations andtests and taken corrective measures described in the Ownersf Report in accordance with the InspectionPlan and as required by the ASME Code, Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed orimplied, concerning the examinations, test, and corrective measures described in this Ownersi Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personaln or property dam e or a loss of any kind arising from or connected with this inspection
An vN jy Commissions NC 978
Inspector's Signature National Board, State, Province, and Endorsements
Date 20......... 2-Z"".... 20
* The Hartford Steam Boiler Inspection & Insurance Company of Connecticut (HSB CT)200) Ashford Center NorthSuite 205Atlanta, GA. 30338
Page 3 of 20
Steam Generator Tubes InspectedCatawba Unit 2 EOC14
The following describes the scope of the Inspection performed at CatawbaUnit 2 for EOC-14 in March 2006:
A bobbin coil eddy current inspection was performed at Catawba Unit 2 EOC-14 inMarch 2006. The tubes selected for the bobbin inspection included tubes withprevious indications, tubes on the periphery of the bundle two rows deep, tubessurrounding plugged tubes and a minimum sample of 20 % of remaining tubesincluding all tubes not inspected with bobbin since EOC -10. During the outageadditional tubes were added to the inspection plan to bound possible loose partsidentified by eddy current and visual inspection. The total tubes inspected by bobbinper steam generator can be found in Table 1.
The tubesheet region was inspected with the array probe. The tubes selected for theinspection included a 20 % random sample, all periphery tubes, all of the historicaloverexpansions and 20 % of the newly identified overexpansions. Relative to thelatter, there was a new criterion developed to more consistently identifyoverexpansions. The tubesheet inspection was performed from two inches above thetop of tubesheet through the tube end. The total number of tubes inspected by thearray probe in the tubesheet region per steam generator can be found in Table 1.
Small radius u bends were also inspected by the array. The tubes selected include a20 % sample of rows one, two and ten. The tubes selected by the bobbin plan in row 3and 4 were also inspected with the array. Row ten is the first row that was notstressed relieved after bending and was sampled for monitoring purposes. The totalnumber of tubes inspected by the array in the u-bends per steam generator can befound in Table 1.
Bobbin coil indications of special interest were also inspected by the array probe. Theindication selected for array special interest were degradation identified during theinspection (I-codes, PLP, and permeability variations), 50% of previously identifieddents greater than two volts, new dents and new wear. The number of tubesinspected for special interest per steam generator can be found in Table 1.
Preheater expansions were also inspected by the array probe. The tubes selected forthe inspection include 20 % the tubes expanded at the 17C and 18C tube supportplate. The total number of tubes inspected by the array in this region per steamgenerator can be found in Table 1.
Tubes were inspected at baffle 18 C by the array probe. This region acts as a looseparts collector since it is at the bottom of the preheater. The total number of tubes
Page 4 of 20
inspected by the array probe in this region per steam generator can be found inTable 1.
Rolled plugs were inspected with a rotating coil probe on the hot leg. Twenty percentof the rolled plugs installed on the hot leg were inspected. The total number of tubeswith rolled plug examinations per steam generator can be found in Table 1.
All plugs were inspected visually on both the hot and cold leg sides. The totalnumber of plugged tubes visually inspected per steam generator can be found inTable 1.
There are 4578 tubes in each steam generator.
Table 1Tubes Inspected by Steam Generator
By Inspection Plan
Scope SG A SG B SG C SG DBobbin 2508 2499 2376 2601Tubesheet 1508 1159 1091 1265(array)Small radius 186 204 177 197u bends(array)Preheater 28 28 28 28expansions at17 C and 18C(array)18 C baffle 97 134 190 130region (array)Special 560 359 362 521Interest ofbobbin(array)Plug (rpc) 11 7 7 8Plug (visual) 68 90 53 85
As. an mo a " all all 011 U " ft In al a M so as As AN a
0
Column 114a
Rowi10
Column 1
Attachments:
A SG 2A Eddy Current Indications and Anomalies
B SG 2B Eddy Current Indications and Anomalies
C SG 2C Eddy Current Indications and Anomalies
D SG 2D Eddy Current Indications and Anomalies
Page 8 of 20
Attachment ASG 2A Eddy Current Indications and Anomalies
Indication CodesSG-ACatawba Unit 2 D5 EOC14Ind Type DescriptionSAI Indication Single Axial IndicationTWD Through WallWAR Wear
Inspection techniques utilized:
BobbinThese codes are used in the following eddy current report for steam generator 2A.
Note: The reported tube indications are for those that were determined to be active inthat they are service related. All original baseline indications are not reported here.
Page 9 of 20
Active degradation for Steam Generator ASG ROW COL VOLTS DEG CHN IND %TW LOCATION UTIL 1 UTIL 2A 7 23 1.59 65 170 SAl TEH +0.00
Attachment BSG 2B Eddy Current Indications and Anomalies
Indication CodesSG-BCatawba Unit 2 D5 EOC14Ind Type Description
CHG Change in IndicationMAI Indication Multiple Axial IndicationNEX Anomaly No ExpansionNQI Indication Non-Quantifiable IndicationOR Data QualitySAI Indication Single Axial IndicationSCI Indication Single Circumferential IndicationSVI Indication Single Volumetric IndicationTWD Through WallWAR Wear
These codes are used in the following eddy current report for steam generator 2B.
Note: The reported tube indications are for those that were determined to be active in
that they are service related. All original baseline indications are not reported here.
Page 13 of 20
Active degradation for Steam Generator BSG ROW COL VOLTS DEG CHN IND %/oTW LOCATION
Attachment CSG 2C Eddy Current Indications and Anomalies
Indication CodesSG - CCatawba Unit 2 D5 EOC14Ind Type Description
CHG Change in IndicationNQI Indication Non-Quantifiable IndicationSAI Indication Single Axial IndicationSVI Indication Single Volumetric IndicationTWD Through WallVOL VolumetricWAR Wear
These codes are used in the following eddy current report for steam generator 2C.
Note: The reported tube indications are for those that were determined to be active inthat they are service related. All original baseline indications are not reported here.
Er
Page 16 of 20
Active degradation for Steam Generator CSG ROW COL VOLTS DEG
Attachment DSG 2D Eddy Current Indications and Anomalies
Indication CodesSG - DCatawba Unit 2 D5 EOC14Ind Type Description
MAI Indication Multiple Axial IndicationNQI Indication Non-Quantifiable IndicationSCI Indication Single Circumferential IndicationTWD Through WallVOL Indication VolumetricWAR Wear
These codes are used in the following eddy current report for steam generator 2D.
Note: The reported tube indications are for those that were determined to be active inthat they are service related. All original baseline indications are not reported here.
4 Page 19 of 20
Active degradation for SteanSG ROW COL VOLTS DEG CHN IND
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